Skip to Main Content
Skip Nav Destination
ASTM Selected Technical Papers
Zirconium in the Nuclear Industry
By
RB Adamson
RB Adamson
1
General Electric Company
,
Pleasanton, California
;
symposium chairman and co-editor
Search for other works by this author on:
LFP Van Swam
LFP Van Swam
2
Exxon Nuclear Company, Inc.
,
Richland, Washington
;
symposium editorial chairman and co-editor
Search for other works by this author on:
ISBN-10:
0-8031-0935-0
ISBN:
978-0-8031-0935-3
No. of Pages:
846
Publisher:
ASTM International
Publication date:
1987

The elastic, plastic, and thermal properties of zirconium-base alloys are highly anisotropic. Consequently, thermomechanical treatments will leave fabricated components with high residual stresses. These stresses play an important role in determining subsequent mechanical properties and the dimensional stability of reactor-core components. When a component is deformed or subjected to a change in temperature, the total strain in any given grain will be accommodated elastically, plastically by shear on the active slip systems or by twinning, and by thermal expansion. The partitioning among the three modes depends not only on the particular orientation of the grain but also on the orientation of the other grains (texture) in the component. A self-consistent analysis, based on the concept of the hcp single-crystal yield surface, has been developed to predict the way that grains in a textured polycrystal respond to arbitrary external thermal or mechanical loading. The calculation follows the elastic-plastic evolution of strain inside each grain, taking into account the anisotropic elastic constants and thermal expansion coefficients. Workhardening due to shear on the active slip systems is included explicitly in the analysis.

Specific examples of the residual stresses produced by tension-compression deformation and thermal cycling of Zircaloy-2 rod will be described. It will be shown that the elastic-plastic transition in Zircaloy-2 requires much larger uniaxial strain and results in much higher apparent workhardening rates than in fcc metals. The predictions will be compared with experimental measurements of residual stresses made using the technique of neutron diffraction.

1.
Piercy
,
G. R.
,
Journal of Nuclear Materials
, Vol.
26
,
1968
, pp. 18-50.
2.
Blackburn
,
W. S.
,
Harnby
,
G.
, and
Stobo
,
J. J.
,
Journal of Nuclear Energy, Part A: Reactor Science
, Vol.
12
,
1960
, pp. 162-171.
3.
Blackburn
,
W. S.
,
Philosophical Magazine
, Vol.
6
,
1961
, pp. 503-508.
4.
Taylor
,
G. I.
,
Journal of the Institute of Metals
, Vol.
62
,
1938
, p. 307.
5.
Bishop
,
J. F. W.
and
Hill
,
R.
,
Philosophical Magazine
, Vol.
42
,
1951
, pp. 414, 1298.
6.
Lin
,
T. H.
,
Journal of the Mechanics and Physics of Solids
, Vol.
5
,
1957
, p. 143.
7.
Kröner
,
E.
,
Acta Metallurgica
, Vol.
9
,
1961
, p. 155.
8.
Budiansky
,
B.
and
Wu
,
T. T.
in
Proceedings
,
4th Congress of Applied Mechanics
,
1962
, p. 1175.
9.
Hill
,
R.
,
Journal of the Mechanics and Physics of Solids
, Vol.
13
,
1965
, p. 89.
10.
Berveiller
,
M.
and
Zaoui
,
A.
,
Comportements Rhéologiques et Structure des Matériaux
, CR 15ième,
Coll. GFR
,
Paris
,
1980
, p. 175.
11.
Hutchinson
,
J. W.
,
Proceedings of the Royal Society
(
London
), Vol.
A319
,
1970
, pp. 247-272.
12.
Hutchinson
,
J. W.
,
Metallurgical Transactions A
, Vol.
8A
,
1977
, pp. 1465-1469.
13.
Holt
,
R. A.
and
Ibrahim
,
E. F.
,
Acta Metallurgica
, Vol.
27
,
1979
, pp. 1319-1328.
14.
Savino
,
E. J.
and
Harriague
,
S.
in
Effects of Radiation on Materials: Twelfth International Symposium
, ASTM STP 870,
American Society for Testing and Materials
,
Philadelphia
,
1985
, pp. 667-689.
15.
Adams
,
B. L.
,
Clevinger
,
G. S.
, and
Hirth
,
J. P.
,
Journal of Nuclear Materials
, Vol.
90
,
1980
, pp. 75-88.
16.
Adams
,
B. L.
and
Murty
,
K. L.
in
Mechanical Behaviour of Materials—IV
,
Proceedings of 4th International Conference
,
Stockholm
,
08
1983
, p. 1252.
17.
Kocks
,
U. F.
,
Metallurgical Transactions
, Vol.
1
,
1970
, pp. 1121-1143.
18.
Tomé
,
C.
and
MacEwen
,
S. R.
, to be published.
19.
Rapperport
,
E. J.
and
Hartley
,
C. S.
,
Transactions of AIME
, Vol.
218
,
1960
, p. 869.
20.
Akhtar
,
A.
and
Teghtsoonian
A.
,
Acta Metallurgica
, Vol.
19
,
1971
, p. 655.
21.
Akhtar
,
A.
,
Acta Metallurgica
, Vol.
21
,
1973
, p. 1.
22.
Fisher
,
E. S.
and
Renken
,
C. J.
,
Physical Reviews
, Vol.
135
,
1964
, pp. A482-A494.
23.
MacEwen
,
S. R.
,
Tomé
,
C.
, and
Faber
,
J.
 Jr.
, to be published.
24.
Akhtar
,
A.
,
Journal of Nuclear Materials
, Vol.
47
,
1973
, p. 19.
25.
Ballinger
,
R. G.
,
The Anisotropic Mechanical Behaviour of Zircaloy-2
,
Garland Publishing
,
New York
,
1979
.
26.
Pelloux
,
R. M.
,
Ballinger
,
P. G.
, and
Lucas
,
G.
, “
The Effects of Anisotropy and Irradiation on the Deformation Behavior of Zircaloy-2
,” EPRI NP-982,
Electric Power Research Institute
,
Palo Alto, Calif.
,
1979
.
27.
MacEwen
,
S. R.
and
Faber
,
J.
, Jr.
in
Proceedings
,
Symposium on Neutron Scattering, Hahn-Meitner Institute HMI-B 411
,
Berlin
,
1984
, pp. 53-57.
28.
MacEwen
,
S. R.
,
Faber
,
J.
, Jr.
, and
Turner
,
A. P. L.
,
Acta Metallurgica
, Vol.
31
,
1983
, pp. 657-676.
29.
MacEwen
,
S. R.
,
Faber
,
J.
, Jr.
, and
Turner
,
A. P. L.
,
Scripta Metallurgica
, Vol.
18
,
1984
, pp. 629-633.
30.
MacEwen
,
S. R.
,
Ells
,
C. E.
, and
Woo
,
O. T.
,
Journal of Nuclear Materials
, Vol.
101
,
1981
, pp. 336-349.
31.
Kocks
,
U. F.
, private communication.
This content is only available via PDF.
You do not currently have access to this chapter.
Close Modal

or Create an Account

Close Modal
Close Modal